Abstract We report here the results of a measurement of the scattered versus unscattered neutron fluence on polyethylene determined via neutron activation of multiple natural indium foils from a deuterium-deuterium (D-D) neutron generator. The neutrons were produced by the High Flux Neutron Generator (HFNG) at the University of California, Berkeley, a specially designed source to maximize neutron flux on a sample while minimizing the total neutron yield. During the experiment, approximately 108 n/s were produced with the energies at the indium foils ranging from 2.2 to 2.8 MeV. Both the angle-integrated and the partial angle differential results are consistent with the predictions of the Monte Carlo N-Particle Transport (MCNP) code, using ENDF/B-VII.1. This supports shielding calculations in the fast energy region with high-density polyethylene.

中文翻译：

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聚乙烯在高通量DD中子发生器中铟箔中使用辐射俘获的整体实验

摘要 我们在此报告了通过来自氘-氘 (DD) 中子发生器的多个天然铟箔的中子活化确定的聚乙烯上散射与非散射中子注量的测量结果。中子由加州大学伯克利分校的高通量中子发生器 (HFNG) 产生，这是一种专门设计的源，可最大限度地提高样品上的中子通量，同时最大限度地降低总中子产量。在实验过程中，在铟箔上产生了大约 108 n/s 的能量，范围从 2.2 到 2.8 MeV。角度积分和部分角度微分结果都与使用 ENDF/B-VII.1 的蒙特卡洛 N 粒子传输 (MCNP) 代码的预测一致。这支持使用高密度聚乙烯在快能区进行屏蔽计算。